GB1321646A - Process for surface treatment of zirconium-containing cladding materials for fuel elements or other components for nuclear reactors - Google Patents

Process for surface treatment of zirconium-containing cladding materials for fuel elements or other components for nuclear reactors

Info

Publication number
GB1321646A
GB1321646A GB3238570A GB3238570A GB1321646A GB 1321646 A GB1321646 A GB 1321646A GB 3238570 A GB3238570 A GB 3238570A GB 3238570 A GB3238570 A GB 3238570A GB 1321646 A GB1321646 A GB 1321646A
Authority
GB
United Kingdom
Prior art keywords
anodic oxidation
fluoride
fuel elements
components
nuclear reactors
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB3238570A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Institutt for Atomenergi
Original Assignee
Institutt for Atomenergi
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Priority claimed from NO282169A external-priority patent/NO122049B/no
Priority claimed from NO512569A external-priority patent/NO123007B/no
Application filed by Institutt for Atomenergi filed Critical Institutt for Atomenergi
Publication of GB1321646A publication Critical patent/GB1321646A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25D—PROCESSES FOR THE ELECTROLYTIC OR ELECTROPHORETIC PRODUCTION OF COATINGS; ELECTROFORMING; APPARATUS THEREFOR
    • C25D11/00—Electrolytic coating by surface reaction, i.e. forming conversion layers
    • C25D11/02—Anodisation
    • C25D11/26—Anodisation of refractory metals or alloys based thereon
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • Electrochemistry (AREA)
  • Materials Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Chemical Treatment Of Metals (AREA)
  • Cleaning And De-Greasing Of Metallic Materials By Chemical Methods (AREA)
  • Treatment Of Steel In Its Molten State (AREA)
  • Heat Treatment Of Articles (AREA)

Abstract

1321646 Anodizing zirconium alloy cladding INSTITUTT FOR ATOMENERGI 3 July 1970 [5 July 1969 24 Dec 1969] 32385/70 Headings C7A and C7B] Zr-base cladding material for fuel elements e.g. of VO 2 or other components for nuclear reactors is surface-treated by pickling in an aqueous fluoride-containing bath, e.g. an aqueous solution of HNO 3 and HF or NH 4 F removing or rendering harmless fluoride-containing contaminants remaining on the surface of the material by anodic oxidation, and oxidizing to apply a protective coating, e.g. by treatment with water or steam under 100 atmosphere pressure and at 400‹ C., by heating in O 2 gas or by anodic oxidation. The removal or rendering harmless of fluoride-containing contaminants and the oxidation to apply a protective coating, by anodic oxidation, may be effected in one step, e.g. in an agitated bath containing a 0À01-0À5 molar solution of alkaline electrolyte, preferably 0À1-2À0 weight per cent KoH in water, at a voltage increasing at a rate not more than 10VS to a final voltage at least 30V which is maintained until the current is constant. The anode connector metal may be the same as the anode (Zr) and the cathode may be of Pt group metal or alloy. Anodic oxidation of Zr may be effected in an electrolyte containing 0À5-3% of HNO 3 , HCl, H 2 SO 4 , H 3 PO 4 , formic or acetic acid, Na NO 3 , K 2 Cr 2 O 7 , H 2 CrO 4 , citric or tartaric acid, NH 4 -tartrate or citrate Œ NH 3 , NH 4 OH, LiOH, NaOH, KOH, EDTA + NH 3 , NaNO 2 , NaB 4 O 7 , K 2 CO 3 , Ca (OH) 2 , Ba (OH) 2 , Na 2 HPO 4 , Na 3 PO 4 , K 2 SO 3 , K 2 SO 4 , or Na 2 SO 4 . Zr base alloys are specified containing: (a) 1À52-1À54% Sn, 0À13-0À20% Fe, 0À09% Cr, 0À006-0À05% Ni, (b) 1À0% Cr, 0À16% Fe; (c) 2À5% Nb, 0À5% Ta; (d) 0À7% V, 0À75% Fe; (e) 1À2% Cu, 0À3% Fe; and (f) 0À2% Sn, 0À09% Fe, 0À07% Ni, 0À14% Nb.
GB3238570A 1969-07-05 1970-07-03 Process for surface treatment of zirconium-containing cladding materials for fuel elements or other components for nuclear reactors Expired GB1321646A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
NO282169A NO122049B (en) 1969-07-05 1969-07-05
NO512569A NO123007B (en) 1969-12-24 1969-12-24

Publications (1)

Publication Number Publication Date
GB1321646A true GB1321646A (en) 1973-06-27

Family

ID=26647475

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3238570A Expired GB1321646A (en) 1969-07-05 1970-07-03 Process for surface treatment of zirconium-containing cladding materials for fuel elements or other components for nuclear reactors

Country Status (4)

Country Link
DE (1) DE2034863C3 (en)
FR (1) FR2054616B1 (en)
GB (1) GB1321646A (en)
SE (1) SE363186B (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113463161A (en) * 2021-07-27 2021-10-01 燕山大学 Anodic oxidation treatment method for zirconium and zirconium alloy surface

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA944716A (en) * 1971-02-03 1974-04-02 Stuart D. Bresnick Method for reducing hydrogen absorption of zirconium by anodizing
EP0488027B2 (en) † 1990-11-28 2008-12-31 Hitachi Ltd. Method of manufacturing a zirconium based alloy fuel channel box
US5264109A (en) * 1991-09-16 1993-11-23 Siemens Power Corporation Zirconium and zirconium alloy passivation process

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1496994C3 (en) * 1965-02-16 1975-10-30 Siemens Ag, 1000 Berlin Und 8000 Muenchen Process for the anodic oxidation of nuclear reactor components made of zirconium

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113463161A (en) * 2021-07-27 2021-10-01 燕山大学 Anodic oxidation treatment method for zirconium and zirconium alloy surface

Also Published As

Publication number Publication date
DE2034863A1 (en) 1971-01-21
DE2034863B2 (en) 1979-06-07
SE363186B (en) 1974-01-07
FR2054616A1 (en) 1971-04-23
DE2034863C3 (en) 1980-02-07
FR2054616B1 (en) 1973-12-07

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee